ML20032B138
| ML20032B138 | |
| Person / Time | |
|---|---|
| Site: | 07000152 |
| Issue date: | 10/20/1981 |
| From: | Crow W, Kosla B NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20032B134 | List: |
| References | |
| NUDOCS 8111040594 | |
| Download: ML20032B138 (8) | |
Text
,
Distribution:
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LTyson WTCrow JBlaylock RErickson DOCKET NO: 70-152 JRobertson APPLICANT: Purdue University (PU)
FACILITY:
West Lafayette, Indiana
SUBJECT:
RENEWAL 0F LICENSE SNM-142
===1.
Background===
Purdue University (PU) was issued License SNM-142 on December 4,1957, authorizing the possession and use of a 3 g U-235 fission counter tube and 160 g of PuBe neutron sources. Subsequently, through amendment and renewal, the possession limit was increased to 113 kg Uranium of various enrichments, 80 g PuBe,11,760 kg natural Uranium and 3 C1 Californium. The majority of the material is used in the operation of a subcritical Fast Breeder Blanket Facility (FBBF) which was evaluated and approved in December 1976, to operate under the condition that the normal Keff not exceed 0.45 and that the accident K,ff not exceed 0.75.
In the blanket mock-up, operable since December 1977, neutron and gamma ray transport is studied, and the experimental studies include measurement of neutron spectra, foil reaction rates, fission -
distribution, and gamma ray heating. Renewal of SNM-142 was requested prior to the expiration-date of January 31, 1979, and the license remains effective under the timely renewal provisions of 70.33(b), 10 CFR 70.
1 The renewal application, prepared before the FBBF was operable..did not reflect the current status of the Purdue facility, and a revised application in the new fomat was requested. The recommended format proposes the use of position description rather than individual resumes and is consistent in style with other SNM licensees, who have demonstrated adequate admini-strative controls to protect the health and safety of their personnel, the public and the environment. The revised application subnittal, dated May 14,1981, requests authorization to possess and use the following material:
Byproduct, source and/or Chemical and/or Maximum amount that Special Nuclear Material Physical Fom Licensee May Possess at Any One Time a,
Uranium enriched in 1.
SPERT fuel rods, 81,000 g the U-235 isotope enriched not to exceed 4.8 weight percent 2.
Fuel rods, enriched 32,000 g not to exceed 1.3 weight percent sua m )
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Solid helices, enriched 200 g not to exceed 20 weight percent 4.
Solid discs, enriched 10 g not to exceed 3 weight percent b.
Plutonium 1.
Encapsulated PuBe neutron 80 g sources Monsanto Mound Lab, Ser. #M-343, M-334, M-345, M-346, & M-347 2.
Waste as metal, salts 19 and nitrate or chloride solution c.
Natural Uranium 1.
U02 pellets clad 11,760,000 g d.
Californium 1.
Up to 10 doubly encap-0.007 g sulated sources. Oak Ridge National Laboratories Sources Ser. #NSD 94, 95, 96 & 97 II. Scope of Review The safety review of Purdue's application for renewal included an examination of previous applications and amendments, a review of the revised application dated May 14, 1981 and addenda dated August 12, 1981 and September 16, 1981, a study of the compliance history and a site visit (January 12-14, 1981) with Region III inspection personnel. The findings are discussed below.
- III.. Discussion of Review Purdue's revised renewal application demonstrates that they have the necessary technical staff with the qualifications to administer an effective and safe radiological protection program. The following sections contain a description of PU's organization and radiological safety program, along with additional conditions developed by FCUP staff.
A.
Administration 1.
The Radiological Control Committee (RCC) was established by the President of Purdue in 1951. Purdue University's FBBF is ins Dev rbueni.
under Ine direct coni.rui of che hociear Engine =
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.....as..aut lor.ized.by..the.RCC...The.. Herd.of...thc.D. epa.tment..of..fluc.1 co r......
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' 007 2 o 193; Engineering appoints the Director of the FBBF facility.
In recent years there have been no significant changes in the structure of this stable operation.
2.
The RCC is composed of the Chairman (appointed by the University President), a qualified Radiological Control Officer, and repre-sentatives from departments whose expertise may be of value to the committee. The duties and responsibilities, including review of all procedures involving SNM as well as the frequency of RCC meetings, are explicitly defined in the application.
3.
The Radiological Control Officer (RC0) is a member of the RCC and has responsibility for the radiation safety review of all procedures presented to the RCC. The minimum education and experience re-quirements for the orincipal members of the radiation safety staff are:
Post baccalaureat degree training and adequate experience, consisting of 30 creait hours (450 contact hours) of health physics training in the following subjects and related areas or its equivalent through job experience:
1.
Principles and practices of radiation protection 2.
Radioactive measurements, monitoring techniques, and instrumentation 3.
Mathenatics and calculations basic to the use and measurement of radioactivity 4.
Biological effects of radiation In addition, persons filling these positions shall have a minimum of two years' practical experience in the safe use of isotopes and/or
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practical health physics experience.
Adherence to the administrative and organizational conditions of the application is amply demonstrated by the calibre of the Radiological Services Staff, as they were observed by FCUP staff.
Further dedication to radiation safety is evident in the minutes of the RCC meetings.
B.
Training Radiation safety training is required for all new employees and/or students.
The principles of radiation safety, as required by 10 CFR 19, are covered in a slide and tape presentation which was developed by the RCO.
In addition, the students, whose study is associated with the FBBF, receive training via formal classroom instruction and testing in nuclear engineering. Refresher seminars which cover radiation safciy prosedures are reqtired en an an nual basis.
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Criticality The FBBF control and operating procedures are under the direct control of the Department of Nuclear Engineering. Measurements af ter fuel loading showed a keff of 0.402, and the maximum calculated keff under flooded conditions is 0.71.
No changes in the current model were proposed in the application; therefore, it is recommended that the existing conditi6nJgoverning criticality be continued as follows:
Condition 11. The Fast Bredder Blanket Facility shall n6t be operated with a measured normal breater than 0.45.
In operation k ff addition,t$efubiloadingshallbelimited such'that the calculated keff w uld not exceed 0.75 if the FBBF were accidentally flooded with water.
t The area monitors.in the FBBF facility meet the requirements of 10 CFR 70.24; however, the aoplicant has requested, pursuant to 10 CFR 70.24(a), an exemption from the provisions of 10 CFR 70.24 for fuel' stored in Rooms B-84 and B-77A. The request is for storage only of fuel containing uranium enriched to less than 5 weight percent U-235 in safe geometry racks. The' staff has determined that granting such an exemption will not endanger public life.or property or the common defense and security and is otherwise in the public interest.
This exemption.is. authorized pursuant to 10 CFR 70.14, in the following condition:
Condition 12. The licensee is exempt from the requirements of Section 70.24,10 CFR 70, insofar as the Section applies.to the stored raaterial in Duncan Annex.
"D.' Radiation Safey Responsibility for radiological health and safety is the duty of the RCC. -Tho RC0, as a member of the RCC, has been delegated responsibility for dissemination of information, proposal review, radiation surveys, monitoring of personnel and the facility, and the overall direction of the radiation safety program.
The structure of review and inspection by the radiation safety office is an affirmation of PU's policy commitment to ALARA.
1.
Personnel Monitoring a.
Exposure, internal and external 1.
There is no formal bioassay program because the potential ror generaung al roorne acu v uy concen-
- r.ations..to a. signif.icant. level..by..the.fEBE.. opera tion.
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monitored and breathing zone samplers are appropriately placed near hoods where work is occassionally performed on fuel rods. Monitoring ecords show no measurable kh gg g jodtah U E sa b r h ajs$ p ggggd jo g any airborne concentration as a result of leacge.
2.
External exposure is evalua reg on the basis of data from film badges which are read once a month.
In addition, use of criticality foils is rec. ired in the FBBF facility and pocket dosimeters are used for temporary or occasional. occupancy. An examination of records during the last inspection showed no measurable whole body dose to anyone associated
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with the FB8F.
b.
Personal Contamination Suitable clothing (lab coats, gloves, etc.,-specifi6 to the job) is used as required. Hands, feet, and clothing are monitored when leaving a lab in which radioisotopes are used. Contaminated clothing must be left behind in the lab and skin decontamination proceeds until the contamination levels return to background level. There is no reporting procedure described in the event that these levels cannot be
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achieved; therefore, the following condition is ~
recommended:
1
,e Condition 13. Persons shall not exit a6 area I,
if personal clothing and/or skin concentration levels are C
above background levels except by approval of the Radiological Control Officer. ~-
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Surface Contamination
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The licensee requires that surface decontaminatio/,
n begin when contamination which is surveyed monthly, j exceeds the action levels specified in the followins table:
Maximum Removable.^
Nuclide Average 2
2 2'
U-nat 5',000 dpm /100 15000 dpm /cm f' 1000 dpni ?!cm U-235 5,000 dpm /100 150.00 dpm /cm2 1000-dpm /cm2 2
2 2
Trans-100 dpm /100cm 3C0 dpm /cm2 20 dpm /cm g
uranics t
The action levels of PU are comparable to levels at allowable contamination developed by NMSS-staff for felease of facilities for unrestricted use; therefore, they are acceptable to this reviewer. The decontamination arocedures are well defined omen eurum)
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,.p-in the application as they apply to surface and personal decontamination; however, there is a defirienty _in the lack of criteria for releasing contaminated equipment and packages from the
,, j' facility for unrestricted use. To correct this y deficiency, the following condition is recommended:
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Conditjon14 Release of equipment or material from Purdue University for unre-
"' f stricted use shall be in accordance f
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with the enclosed Annex A, " Guide-k lines for Decontamination of Facilities
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And Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct. Source, or Special nuclear Material," published-j
" by the US NRC Division rif Fuel Cycle and Material Safety, dated November 1976.
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Calibration To insure that the radiation detecting instruments function properly, the instruments are calibrated every six months with a')propriate standards as suggested in Reg. Guide 10.3.
A e.
Leak Testing Leak testing at the"Pequired intervals is confirned by PU record 1.
A general requirement of all our licensees is the
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following condition:
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Ceddition 15. The licensee shall comply with the enclosed Annex B, ' dated September
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1960, " License Condition. For Leak = ~
Testing Sealed Platonium Sources."
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a Contaminated waste from SNM use is removed and disposed of, after volume reduction when possible, to a licensed burial ground in confomance
' with NRC and DOT regulations.
l.
F.
Se'c$rity_
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The Physical Security Licensing Branch has reviewed the security pldn suttaitted by PU and has ' determined that the plan meets the
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re.pirements 6f 10 CFR-73.67 ~for SNM of moderate strategic significance, 50Djeht to the following condition:
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< Condition 16. The licensee shall follow Revisions 1 and 2 to tne aecurity Vian for tne ruraue university j"'"k ;'...g.............L,.............
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the Nuclear Storage Areas," dated March 31, 1980 and October 24, 1980, respectively.
IV.
Comoliance History, a_r.d IE_C_cmm_en_t.s A review of the Inspection and Enforcement record of the Smi license under examination was basicly positive. One malfunctioning criticality monitor was an item of no compliance epcrted in the bl9 inspection.
It was corrected and no items of non-compliance were reported in the recent 1981 inspection.
Comments from Inspector Charles Peck, Region III, IE, at the time of the last inspection were favorable tuara the radiation safety program. On October 2,1981, the proposed renewed license was discussed with Mr. Peck, and he has no objection to the-issuance of the renewed license as described in the PU revised application and the proposed additional conditions.
V.
Conclusion Upon completion of tha radiation safety review and the compliance history, the staff concludes that the basis of the radiation safety program is sound.
Confonnance by Purdue University with their proposed conditions as well as those developed by the FCUF staff should insure a safe operation and quick detection of unfavorable trends or effects by PU or IE with prompt corrective action.
Based on this analysis, it is concluded that the proposed renewal application is non-substantive and insig dficant from the standpoint of environmental impact, and pursuant to subparagraph 51.5(d)(3) of 10 CFR 51, no environmental impact statement, negative declaration, or environmental impact appraisal need be prepared.
Based on the discussion above, it is therefore recommended that the licen:e be renewed for a five-year period in accordance with tihe.applicet. ion and subject to the following conditions:
Condition 11.
The Fast Breeder Blanket Facility shall not ce operated with a measured normal operation keff greater than 0.45.
In addition, the fuel loading shall be limited such that the calculated k would not exceed 0.75 if the FBBF were accibtally flooded with water.
Condition 12.
The licensee is exempt from the requirements of Section 70.24.10 CFR 70, inso ar as the f
Section apolies to the stored material in Duncan Annex.
Condition 13.
Persons shall not exit an area if personal clothing and/or skin concentration levels are above background levels except by approval of the Radiological Control Officer.
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0E Condition 14.
Release of equipment or material from Purdue
' University for unrestricted use shall be in accordance with the enclosed Annex A,
'" Guidelines for Decontamination of Facilities
..And Yquipment Prior to Release for Urrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material," published by the US NRC Division of Fuel Cycle and Matarial Safety, dated November 1976.
Condition 15. The licensee shall comply with the enclosed Annex B dated September 1980, " License Condition. For Leak Testing Sealed. Plutonium Sources."
Condition 16. The licensee shall follow Revisions 1 and E to
'the " Security Plan for the Purdue University aheector, the Fast Breeder Blanket Facility and the Nuclear Storage Areas," dated March 31, 1980 and October 24, 1980, respectively, Y
original SIPO B. L Kosla "'
B. M. Kosla Uranium Process Licensing Section Uranium cuel Licensing Branch Division of Fuel Cycle and Original signed bit fiaterial Safety Approved by:
L T. crow W. T. Crow, Section Leader
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